ML12342A086
| ML12342A086 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 12/06/2012 |
| From: | NRC/RGN-II |
| To: | Southern Co |
| References | |
| Download: ML12342A086 (61) | |
Text
DRAFT Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM ADMIN 1 = SRO ONLY TITLE VERIFY FUEL MOVEMENT SHEET AUTHOR MEDIA NUMBER TIME Error! Reference source not 2012-301 ADMIN-1 30 Minutes found.
RECOMMENDED BY APPROVED BY DATE N/R SOUTHERNA COMPANY
SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH Page 1 of 1 FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code:
OPERATIONS TRAINING Media Number:
2012-301 ADMIN-1 Initial development Reason for Revision Revision for use on 2012-30 1 NRC Exam. After NRC Exam, Media Number will be changed to LR-JP-45.33A.
Authors Initials FNF ARB Supvs Initials Rev.
No.
Date 00 03/17/09 01
2012-301 ADMIN-1 Page 1 of 6 UNIT 1 (X)
UNIT 2 (X)
TASK TITLE:
VERIFY FUEL MOVEMENT SHEET JPM NUMBER:
2012-301 ADMIN-1 TASK STANDARD:
Verify proper fuel movements.
TASK NUMBER:
045.033 OBJECTIVE NUMBER:
045.033.0 PLANT HATCH JTA IMPORTANCE RATING:
RO Not Available SRO Not Available K/A CATALOG NUMBER: G2.1.35 K/A CATALOG JTA IMPORTANCE RATING:
RO 2.2 SRO 3.9 OPERATOR APPLICABILITY:
Senior Reactor Operator GENERAL
REFERENCES:
Refuel Floor 34FH-OPS-001-0 (current version) 42FH-ERP-014-0 (current version)
REQUIRED MATERIALS:
Refuel Floor Fuel Movement Sheets 34FH-OPS-001-0 (current version) 42FH-ERP-0 14-0 (current version)
APPROXIMATE COMPLETION TIME:
30 Minutes SIMULATOR SETUP:
N/A
EVALUATOR COPY UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:
1.
Unit 2 is in a refueling outage.
2.
You are the oncoming Refuel Floor SRO.
3.
The off-going Refuel Floor SRO asks you to verify Page 1 of the attached Fuel Movement Sheet.
4.
The fuel movement sheet, Core Map and pictures of the core cells are available.
INITIATING CUES:
Verify the in-core placement of all components listed on Page 1 of the attached Fuel Movement Sheet.
2012-301 ADMIN-1 Page 3 of 6 STEP PERFORMANCE STEP STANDARD I
(COMMENTS)
For INITIAL Operator Programs:
For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.
IF THEN IJ Human performance tools, safety, PPE met (1), AND D
Mark the JPM as a PASS LI For initial trg all steps completed correctly OR PASS LI For continuing trg, critical steps (if used) completed correctly FAIL LI Above standards not met LI Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.
Reference:
NMP-TR-1 11, On-The-Job Training and Task Performance Evaluation.
START TIME:________
PROMPT:
PROMPT:
PROMPT:
Hand the operator the fuel movement sheet, Core Map and pictures of the core cells.
IF the operator has problems reading the bundle serial numbers, THEN provide the serial numbers to the operator.
IF the operator asks about Spent Fuel Pool verification, THEN tell the operator he is only responsible for in-core verifications.
1.
Obtains the correct procedures.
Obtains and reviews 42FH-ERP-014-0, Fuel Movement and 34FH-OPS-001-0, Fuel Movement Operation.
(** Indicates critical step)
2012-301 ADMIN-1 Page 4 of 6 STEP PERFORMANCE STEP STANDARD I
(COMMENTS)
- I 2.
Verify correct loading of Control Cell Operator determines Control Cell 38-37.
38-37 bundles are the correct bundles and in the correct orientation:
- JLV675
- JLV682
- JLK8O4
- JLK817
- 3 Determine INCORRECT loading of Operator determines Control Cell Control Cell 14-37.
14-37 bundles are the correct bundles but in the INCORRECT orientation:
e JLV678
- JLV67O NOTE: Bundles JLV678 and JLV67O are 180° out.
4.
Verify correct loading of Control Cell Operator determines Control Cell 14-37.
14-37 bundles are the correct bundles and in the correct orientation:
- JLK8O5
- JLK812
- 5*
Determine INCORRECT loading of Operator determines Control Cell Control Cell 38-17.
38-17 bundle is the INCORRECT bundle but in the correct orientation:
- JLV668 NOTE: Wrong bundle loaded. The correct bundle is JLV698
( Indicates critical step)
2012-301 ADMIN-1 Page 5 of 6 STEP I
I SAT!UNSAT 1
I PERFORMANCE STEP STANDARD (COMMENTS)
I 6.
Verify correct loading of Control Cell Operator determines Control Cell 38-17.
14-37 bundles are the correct bundles and in the correct orientation:
. JLV674
- JLK8O7
- JLK82O
- 7 Determine INCORRECT loading of Operator determines Control Cell Control Cell 14-17.
14-17 Double Blade Guide is in the INCORRECT orientation.
NOTE:
The terminating cue shall be given to the Operator when:
After JPM step #7 is complete.
With no reasonable progress, the Operator exceeds double the allotted time.
Operator states the task is complete.
TERMINATING CUE:
We will stop here.
EVALUATOR PICK UP the Initiating Cue sheet.
END TIME:_______
( Indicates critical step)
UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:
1.
Unit 2 is in a refueling outage.
2.
You are the oncoming Refuel Floor SRO.
3.
The off-going Refuel Floor SRO asks you to verify Page 1 of the attached Fuel Movement Sheet.
4.
The fuel movement sheet, Core Map and pictures of the core cells are available.
INITIATING CUES:
Verify the in-core placement of all components listed on Page 1 of the attached Fuel Movement Sheet.
DRAFT Southern Nuclear E, I Hatch Nuclear Plant Operations Training JPM ADMIN 2 ALL TITLE CORRECT RWL INDICATORS FOR HIGH DRYWELL TEMPERATURES AUTHOR MEDIA NUMBER TIME ANTHONY BALL 2012-301 ADMIN-2 11.0 Minutes RECOMMENDED BY APPROVED BY DATE N/R SOUTHERNA COMPANY
SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH Page 1 of 1 FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code:
OPERATIONS TRAINING Media Number: 2012-301 ADMIN-2 Rev. No.
Date Reason for Revision Authors Supvs Initials Initials 00 Modified from LR-JP-25 101 for use on 2012-301 ARB NRC Exam.
2012-301 ADMIN-2 Page 1 of 9 TASK TITLE:
UNIT 1 (X)
CORRECT RWL INDICATORS FOR HIGH DRYWELL TEMPERATURES UNIT 2 (X)
JPM NUMBER:
TASK STANDARD:
2012-301 ADMIN-2 The task shall be completed when the operator has determined the corrected RWL for the specified instrumentation per 34AB-B2 1-002.
TASK NUMBER:
OBJECTIVE NUMBER:
201.099 201.099.B PLANT HATCH JTA IMPORTANCE RATING:
RO 4.57 SRO 3.83 STA 4.00 K/A CATALOG NUMBER: G2.1.35 K/A CATALOG JTA IMPORTANCE RATING:
RO 3.90 SRO 4.20 OPERATOR APPLICABILITY:
Nuclear Plant Operator (NPO)
GENERAL
REFERENCES:
Unit 1 Unit 2 34AB-B2 1-002-i 34AB-B2 1-002-2 (current version)
(current version) 34AB-B21 -002-1 (current version) 34AB-B2 1-002-2 (current version)
REQUIRED MATERIALS:
Unit 1 Unit 2 APPROXIMATE COMPLETION TIME:
11.0 Minutes SIMULATOR SETUP:
N/A
EVALUATOR COPY UNIT 1 READ TO THE OPERATOR INITIAL CONDITIONS:
The Reactor has scrammed and the board operator has reported the following UNCOMPENSATED Reactor Water Levels:
1B21-R604A and 1B21-R623A (Wide Range) is -125 inches.
1B21-R604B and 1B21-R623B (Wide Range) is -127 inches.
1B21-R623A (Fuel Zone) is -170 inches.
INITIATING CUES:
Determine which of these RWL indications are valid and report the corrected RWL for all valid RWL instrumentation.
2012-301 ADMIN-2 Page 3 of 9 STEP PERFORMANCE STEP STANDARD I
(COMMENTS)
For INITIAL Operator Programs:
For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.
IF THEN U
Human performance tools, safety, PPE met (1), AND U
For initial trg all steps completed correctly OR PASS U
For continuing trg, critical steps (if used) completed correctly FAIL U
Above standards not met U
Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be selfcorrected provided the action would not have resulted in significant actual or potential consequences.
Reference:
NMP-TR-1 11, On-TheJob Training and Task Performance Evaluation.
START TIME:________
1.
Operator identifies the procedure Operator has identified the correct needed to perform the task, procedure as 34AB-B21-002-1.
NOTE: If the operator (STA) indicates that SPDS would be checked, give the operator Supplement 1.
PROMPT:
IF the operator addresses Drywell temperature indications, INDICATE for the operator that temperature is greater than 150°F (Use Supplement I if SPDS is addressed).
2.
Determine if RWL corrections are Using SPDS (or Drywell temp required.
indications) the operator DETERMINES:
Drywell temperature is greater than 150°F.
RWL corrections ARE required.
3.
Review Caution 1 and Caution 2 on The operator has REVIEWED Attachment I of 34AB-B21-002-1.
Caution 1 and Caution 2 on of 34AB-B21-002-l.
(*
- Indicates critical step)
2012-301 ADMIN-2 Page 4 of 9 STEP PERFORMANCE STEP STANDARD I
(COMMENTSH PROMPT:
IF the operator addresses instrument behavior, as the board operator, INFORM the operator that NO erratic behavior for the specified instruments has been observed.
4.
Confirm there is no indication of The operator has VERIFIED, by erratic instrument behavior, observation or by addressing the panel operator, that the following RWL instruments show NO erratic instrument behavior:
1B21-R604A 1B21-R604B 1B21-R623A (Wide Range) 1B21-R623B (Wide Range) 1B21-R623A (Fuel Zone)
PROMPT:
WHEN the operator indicates use of the Diagnostic screen of SPDS, GIVE the operator Supplement 2.
5.
Determine highest temperature for At SPDS panel, the operator has RTD Group I and 2 (Maximum Run DETERMINED the following Temperature).
Maximum Run Temperatures:
RTD Group I
- 260°F RTD Group 2 - 257°F PROMPT:
IF the operator addresses temperature indications on Panels P654 and P657; indications can be SIMULATED using the values from Supplement 2.
- Indicates critical step)
2012-301 ADMIN-2 Page 5 of 9 STEP PERFORMANCE STEP STANDARD I
(COMMENTS)1
- 6.
Determine if the RWL instrument may The operator has DETERMINED be used by comparing the Minimum the following RWL instruments Indicated Level for the associated are VALID:
Maximum Run Temperature.
1B2l-R604A 1B21-R604B 1B21-R623A (Wide Range)
I B21-R623B (Wide Range) 1B21-R623A (Fuel Zone) 1B21-R623B (Fuel Zone)
- 7 Determine corrected Fuel Zone Level Using Attachment 3 of (1B21-R623A).
34AB-B2 1-002-1, the operator has DETERMINED Corrected Level for 1B21-R623A (fuel zone) is -137 inches (accept +/-1 inch).
PROMPT:
IF the Operator informs you that the Wide Range Instruments are not the preferred RWL Instruments for the current RWL, ACKNOWLEDGE and INFORM the Operator to continue with the RWL corrections.
- 8.
Determine Drywell Temperature Using Attachment 4 of Correction Factor for instruments 34AB-B21-002-1, the operator 1B21-R604A and 1B21-R623A has DETERMINED the (Wide Range).
Correction Factor is 8 inches (accept +/-1 inch) for instruments 1B21-R604A and 1B21-R623A (Wide Range).
- 9*
Determine Drywell Temperature Using Attachment 4 of Correction Factor for instruments 34AB-B21-002-1, the operator 1B21-R604B and 1B21-R623B has DETERMINED the (Wide Range).
Correction Factor is 8 inches (accept +/-1 inch) for instruments 1B21-R604B and 1B21-R623B (Wide Range).
(** Indicates critical step)
2012-301 ADMIN-2 Page 6 of 9 STEP I
SAT/UNSAT PERFORMANCE STEP I
STANDARD j
(COMMENTS) 1
- IO.
Determine corrected RWL for the The operator has DETERMINED following Wide Range instruments:
the corrected level for the following Wide Range 1 B21 -R604A instruments:
1B21-R623A (Wide Range) 1B21-R604A is -133 inches (+/-1) 1B21 -R60413 1B21-R623A (Wide Range) is 1B21-R623B (Wide Range)
-133 inches (+/-1) 1B21-R604B is -135 inches (+/-1) 1B21-R623B (Wide Range) is
-135 inches (+/-1)
NOTE: Acceptance +/-1 inch for each corrected level.
END TIME:
NOTE:
The terminating cue shall be given to the Operator when:
After JPM step #10 is complete.
With no reasonable progress, the Operator exceeds double the allotted time.
Operator states the task is complete.
TERMINATING CUE:
We will stop here.
EVALUATOR PICK UP the Initiating Cue sheet.
( Indicates critical step)
Page 7 of 9 UNIT 1 READ TO THE OPERATOR INITIAL CONDITIONS:
1.
The Reactor has scrammed and the board operator has reported the following UNCOMPENSATED Reactor Water Levels:
1B21-R604A and 1B21-R623A (Wide Range) is -125 inches.
1B21-R604B and 1B21-R623B (Wide Range) is -127 inches.
1B21-R623A (Fuel Zone) is -170 inches.
INITIATING CUES:
Determine which of these RWL indications are valid and report the corrected RWL for all valid RWL instrumentation.
SRM I
I0UTI cPS SECONDARY HNP1I___
HNP2I I
MODE: RUN 0
POWER 125 100W 75.
50*
25 0-fl jtCilcc iCiJcc jiCi/cc VENT HNP1 I
I HNP2 I
I STACK N
180 ISOLATION PRIMARY nIALL IALL 90 I
2A 2B 2C2D2E SEC IALL 270 PSIG y3,{IJ 0
SUPPLEMENT 1
_l__
DRYWELL TEMPERATURE NOO4 NOO7 NOD1B NOO1L NOO5 DIAGNOSTIC VOLUMETRIC 12201 DEG. F AVG.
TEMP NOO1J NOD1M N008 NOO1A NOD 1K N002 N003 SUPPLEMENT 2
DRAFT Southern Nuclear K I. Hatch Nuclear Plant Operations Training JPM ADMIN 3 RO ONLY SOUTHERN COMPANY TITLE Anthony Ball Determine if plant conditions allow a Quick Restart of a Recirculation Pump.
AUTHOR MEDIA NUMBER TIME 2012-301 ADMIN-3 15 Minutes RECOMMENDED BY APPROVED BY DATE NR
SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH Page 1 of 1 FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code:
OPERATIONS TRAINING Media Number:
2012-301 ADMIN-3 Rev. No.
Date Reason for Revision Authors Supvs I
Initials Initials 00 Modified from LR-JP-25050 & will become new LR-JP-25053 after NRC Exam.
2012-301 ADMTN-3 Page 2 of 10 UNIT 1 (X)
UNIT 2
()
TASK TITLE:
Determine if plant conditions allow a Quick Restart of a Recirculation Pump.
3PM NUMBER:
2012-301 ADMIN-3 TASK STANDARD:
The task shall be complete when it has been determined that the requirements of 34S0-B31-001-1, Reactor Recirculation System have NOT been met to start a Reactor Recirculation pump.
TASK NUMBER:
004.002 OBJECTIVE NUMBER:
004.002.A K/A CATALOG NUMBER: Generic 2.1.20/Generic 2.1.32 K/A CATALOG JTA IMPORTANCE RATING:
RO 4.3/3.4 SRO 4.2/3.8 OPERATOR APPLICABILITY:
Nuclear Plant Operator (NPO)/Senior Reactor Operator (SRO)
- GENERAL
REFERENCES:
Unit 1 34S0-B3 1 -OPS-00 1-1 (Current Version)
REQUIRED MATERIALS:
Unit 1 3400-OPS-001-1 (Current Revision)
APPROXIMATE COMPLETION TIME:
15 Minutes SIMULATOR SETUP:
N/A, Used for NRC Adrnin JPM (classroom setting)
2012-301 ADMIN-3 Page 3 of 10 EVALUATOR COPY UNIT 1 READ TO THE OPERATOR INITIAL CONDITIONS:
1.
10 minutes ago, the Unit 1 reactor scrammed from 100% power.
2.
Both Reactor Recirculation pumps tripped during the scram transient.
3.
Reactor water level went as low as 10 inches and has been restored to
+37 inches using Reactor Feedwater Pumps.
4.
HPCI and RCIC were not required during the transient and have remained in standby.
5.
RWCU is in service.
6.
The Shift Supervisor has given direction to perform a Quick Restart of the 1B Reactor Recirculation pump to prevent thermal stratification.
7.
An operator has entered 34S0-B31-001-1, Reactor Recirculation System and completed steps 7.1.4.2.1 through 7.1.4.2.5 (Recirc Pump B Quick Re-start).
8.
Data collection began 4 minutes ago and the operator has completed gathering plant data for use with step 7.1.4.2.6 of 34S0-B31-001-l.
INITIATING CUES:
Determine if plant conditions meet the procedural requirements for Quick starting the 1B Reactor Recirculation pump per step 7.1.4.2.6 of 34S0-B3 1-001 -1, Reactor Recirculation System.
2012-301 ADMIN-3 Page4of 10 STEP PERFORMANCE STEP STANDARD I
(COMMENTS)
For INITIAL Operator Programs:
For OJTIO.JE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.
IF THEN U
Human performance tools, safety, PPE met (1), AND U
For initial trg aN steps completed correctly OR PASS U
For continuing trg, critical steps (if used) completed correctly FAIL Li Above standards not met U
Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.
Reference:
NMP-TR-1 11, On-The-Job Training and Task Performance Evaluation.
START TIME:________
NOTE: 34S0-B31-OO1-1, Attachment 6 serves as an answer key for this JPM. It is NOT to be provided to the student.
NOTE: At this time, provide the operator with Attachment 1 (Plant Data page) and a copy of 34S0-B31-001-1.
PROMPT:
IF addressed by the operator, INFORM the operator that the ASD is NOT in local control.
1.
Operator refers to step 7.1.4.2.6 and is Step 7.1.4.2.6 directed to Attachment 6 of 34SO-B31-001-1.
2.
Operator selects B Recirc Pump.
Places a check mark next to B Recirc. Att. 6 Step 1.0 3.
The operator enters the current time.
Records current time.
Att. 6 Step 2.0
- 4, The operator determines RPV Tsat = 521° F (+/-2° F) saturation temperature.
Att. 6 Step 2.0 (A)
(
Indicates critical step)
2012-301 ADMIN-3 Page 5 of 10 STEP PERFORMANCE STEP STANDARD I
(COMMENTS) 1 NOTE: Data is NOT required to be filled in for the 1 A Recirc Pump in the following step.
5.
The Operator enters suction Recirc 1A: 470° F temperature for Recirculation Pumps.
Recirc 1B: 475° F (Att. 6 Step 2.0 (A) & (B))
6.
The operator enters the bottom head Bottom head temperature: 365° F temperature.
(Att. 6 Step 2.0 (D))
7.
The operator calculates the At between At = (5210 F
- 475° F) = 46° F the IB ioop and the RPV.
(+/-2° F) (Att. 6 Step 1.2.1)
- 8.
The operator determines the At At of 46° F (+/-2° F) is < 50° F between the 1B loop and the RPV (Att. 6 Step 3.1)
IS acceptable.
NOTE: The student should NOT use step 4.2 to perform the following confirmation of plant conditions due to the NOTE that precedes step 4.0 (RWCU is in service). If the operator does refer to step 4.2, the check will NOT be acceptable due to Feedwater temperature < 300° F.
- 9*
The operator calculates the At between At = (521° F - 365° F) = 156° F bottom head and steam dome.
(+/-2° F) (Att. 6 Step 4.1)
- 1O.
The operator determines that the At At of 142° F (+/-2° F) is < 145° F between bottom head and steam dome (Att. 6 Step 4.1)
IS acceptable.
11.
The operator reports to the Shift Plant conditions ARE acceptable Supervisor, for starting the 1B Reactor Recirculation pump.
NOTE: Step 4.2 is NOT required to be performed (it is an alternate method). If the student chooses to perform step 4.2, the conditions will NOT allow the start of the Recirc Pump (FW temp <300 F). The following information is expected to be determined by the student (see Attachment for details):
(a) is met (>40% of rated flow prior to the RPT).
(b) is met (HPCI and RCIC have not injected since the RPT)
(c) is NOT met (FW temp is not >300 F since the RPT) is met (<30 minutes since trip) and start time (calculated time to start is required to be 30 minutes from the RPT time)
- Indicates critical step)
2012-301 ADMIN-3 Page 6 of 10 STEP PERFORMANCE STEP STANDARD I
(COMMENTS)
PROMPT:
IF addressed by the operator, as the STA, INFORM the operator that power/flow map conditions are acceptable for starting the Recirc Pump.
PROMPT:
IF addressed by the operator, as the Shift Supervisor, INFORM the operator that another operator will verify his calculations.
END TIME:________
NOTE:
The terminating cue shall be given to the operator when:
After JPM step #11 is complete.
With no reasonable progress, the operator exceeds double the allotted time.
Operator states the task is complete.
TERMINATING CUE:
We will stop here.
EVALUATOR PICK UP the Initiating Cue sheet.
( Indicates critical step)
ti rj-i j.
- j. jj]- j 103 UI LUO DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION No:
REACTOR RECIRCULATION SYSTEM 34S0-B31-001-1 41.1 ATTACHMENT Attachment Page TITLE:
RECJRC PUMP QUICK RE-START LIMIT CHECKS 2 of 4 E9UIEI
[NOTE:
This attachment may be performed in Modes 1, 2, AND 3.
1 1.0 Recirc Loop and RPV Limit Checks:
Pre-startup checks for (v):
A recirc B recirc 2.0 Record the foHowing data: Time CURRENT TIME APPLICANTS INITIALS Parameter Location Value SPDS MISC RPV Heatup/
Cooldown OR Steam Tables
- The Bottom Head Drain temperature (D) may still be used even IF RWCU is NOT in service.
(See Limitation 5.2.14). IF Bottom Head Drain temperature is NOT available, (i.e., inoperable),
THEN use the alternate method of confirming the Bottom Head to Coolant z\\T in step 4.0.
FOR the Recirc loop to be started, confirm the AT between the reactor coolant temperature in the loop AND the RPV coolant temperature is 50°F by performing step3.1 OR 3.2 below:
3.1 IF both recirc loops are idle; Loop A AT = 1(A)
- (B)
=
(acceptable 50°F)
OR Loop B AT = 1(A)
- (C) I
=
46°F (+/-2°F) (acceptable 50°F)
INITIALS
..................................... Qi *..................e..............e..........
3.2 IF only one recirc loop is idle, THEN loop AT = 1(B)
- (C) I
=
(acceptable 50°F)
NA OPS-1321 Ver. N/A EVALUATOR USE ONLY (KEY)
DO NOT give to candidate RPV Saturation Temp.
(A)
(B)
(C)
(D) 521°F (+/-2°F)
(A) 1B31-R650 OR Equivalent, A Recirc Suction Temp average of process computer 470°F (B) points B034, B035 1B3 l-R650 OR Equivalent, B Recirc Suction Temp average of process computer 475°F (C) points B036, B037
- 1B21R606 Pt 3 OR
- Vessel Bottom Head Drain (D) 1G31-N601 Pt5
- 379°F Critical 3.0 NA rrn
G16.030
SNC PLANT E. I. HATCH I Confirm the iT between the bottom head coolant temperature AND the reactor pressure vessel (RPV) coolant temperature is 145°F by performing step 4.1 OR 4.2 below:
z\\T = 1(A)
- (D)
= 142° F (+/-2°F) (acceptable 145°F)
Pg 184 of 208
- .B *.............................................
4.2 Per Tech Spec BASES B.3.4.9, confirm ALL of the following:
(a)
One Q!E more loop drive flows were > 40% (18,000 gpm) of rated flow prior to the RPT, AND NA TRUE (b)
HPCI and RCIC Systems have NOT injected since the RPT, AND NA TRUE (c)
Feedwater temperature has remained > 300°F since the RPT, AND NOT CORRECT (d)
Time between the RPT AND restart is <30 minutes.
These are calculated by the student, based on JPM start time. The time will vary.
Record Recirc RPT trip time:
(Ti)
Recirc start is required prior to:
(Ti) + 30 minutes =
IF only ONE Recirc pump is idle, THEN confirm the operating pump loop flow is <22,500 gpm.
NA Critical 6.0 Confirm the:
(1)
Power/flow condition is acceptable for restart per the STA/Rx Engineering.
INITIALS OR (2)
IF the OPRM System is inoperable, the reactor is 10% below the 61% Load Line of Attachment 1, OPRM System INOP Power vs. Flow map in 34AB-C51-001-1, in order to avoid inadvertent entry into the RPI.
INITIALS DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION No:
REACTOR RECWCULATION SYSThM 34S0-B31-001-1 41.1
(
ATfACHMENT 6 Attachment Page iLE:
RECIRC PUMP QUICK RE-START LIMIT CHECKS 4 of 4 F
IF a direct indication is NOT available for Vessel Bottom Head Drain temp (D),
NOTE:
THEN within 30 minutes of an RPT, the bottom head to coolant zT ( 145°F) may be confirmed per the alternate method in step 4.2.
Critical 4.0 4.1 INITIALS Critical 5.0 EVALUATOR USE ONLY (KE
)
DO NOT give to candidate INITIALS OPS-1321 Ver. N/A G16.030 MGR-0009 Ver. 5
SNC PLANT E. I. HATCH I 7.0 Independently verify the data recorded above is ACCEPTABLE prior to proceeding with the recirc pump start.
Critical Pg 185 of 208 (VERIFIED)
INITIALS 8.0 Confirm the steps 1.0 thru 7.0 above, was performed within the ast 15 minutes.
9.0 Record Recirc pump start time:
OPS-1321 Ver. N/A G16.030 INITIALS INITIALS DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION No:
REACTOR RECIRCULATION SYSTEM 34S0-B31-001-1 41.1 ATFACHMENT Attachment Page iLE:
RECIRC PUMP QUICK RE-START LIMIT CHECKS 4 of 4 EVALUATOR USE ONLY (KEY)
DO NOT give to candidate MGR-0009 Ver. 5
Page 10 of 11 UNIT 1 READ TO THE OPERATOR INITIAL CONDITIONS:
1.
10 minutes ago, the Unit 1 reactor scrammed from 100% power.
2.
Both Reactor Recirculation pumps tripped during the scram transient.
3.
Reactor water level went as low as 10 inches and has been restored to
+37 inches using Reactor Feedwater Pumps.
4.
HPCI and RCIC were not required during the transient and have remained in standby.
5.
RWCU is in service.
6.
The Shift Supervisor has given direction to perform a Quick Restart of the 1B Reactor Recirculation pump to prevent thermal stratification.
7.
An operator has entered 34S0-B31-001-1, Reactor Recirculation System and completed steps 7.1.3.1 through 7.1.3.9 (Recirc Pump A(B)
Quick Restart).
8.
Data collection began 4 minutes ago and the operator has completed gathering plant data for use with step 7.1.3.10 of 34S0-B31-00l-l.
INITIATING CUES:
Determine if plant conditions meet the procedural requirements for starting the 1B Reactor Recirculation pump per step 7.1.4.2.6 of 34S0-B3 1-001-1, Reactor Recirculation System.
Page ii of ii PROVIDE TO APPLICANT 1 Plant Data Reactor pressure: 805 psig A Recirc Suction Temp (1B31-R650): 4700 F B Recirc Suction Temp (1B31-R650):
4750 Vessel Bottom Head Drain (1B21-R606 Pt 3): 379° F Reactor Feedwater temperature:
295° F
DRAFT Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM ADMIN 4 ALL TITLE REVIEW OF HPCI PUMP OPERABILITY SURVEILLANCE AUTHOR MEDIA NUMBER TIME Anthony Ball 2012-301 ADMIN-4 15 Minutes RECOMMENDED BY APPROVED BY DATE SOUTHERNA COMPANY
SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH Page 1 of I FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code:
OPERATIONS TRAINING Media Number: 2012-301 ADMIN-4 1
Authors Supvs Rev. No.
Date i
Reason for Revision I
Initials Initials 00 initial development.
2012-301 ADMIN-4 Page 1 of 12 UNIT 1 (
)
UNIT 2(X)
TASK TITLE:
REVIEW OF HPCI PUMP OPERABILITY SURVEILLANCE JPM NUMBER:
2012-301 ADMTN-4 TASK STANDARD:
The task shall be complete when the operator reviews the completed surveillance procedure, 34SV-E41-002-2, and determines HPCI is inoperable and one PSW valve must be retested or declared inoperable and the other is inoperable.
TASK NUMBER:
300.011 OBJECTIVE NUMBER:
300.011.0 K/A CATALOG NUMBER:
Generic 2.2.12 K/A CATALOG JTA IMPORTANCE RATING:
RO 3.7 SRO 4.1 OPERATOR APPLICABILITY:
Nuclear Plant Operator (NPO) / Senior Reactor Operator (SRO)
GENERAL
REFERENCES:
Unit 2 34SV-E41 -002-2 (current version)
REQUIRED MATERIALS:
Unit 2 Completed surveillance package: 34SV-E41-002-2.
APPROXIMATE COMPLETION TIME:
15 Minutes SIMULATOR SETUP:
N/A
EVALUATOR COPY UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:
1.
Unit 2 is at 100% power.
2.
A HPCI Pump Quarterly 1ST Data Test (1ST) has just been completed for the HPCJ pump JAW 34SV-E41M02-2, HPCI Pump Operability.
INITIATING CUES:
Review Attachment 1 of 34SV-E41-002-2, HPCI Pump Operability.
Complete any calculations required by the surveillance data sheets.
Inform the Shift Supervisor of your results and any recommendations or procedural requirements based on the results.
Page 2 of 12
2012-301 ADMIN-4 Page 3 of 12 STEP PERFORMANCE STEP STANDARD I
(COMMENTS)
For INITIAL Operator Programs:
For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.
IF THEN U
Human performance tools, safety, PPE met (1), AND U
For initial trg all steps completed correctly OR PASS U
For continuing trg, critical steps (if used) completed correctly FAIL U
Above standards not met U
Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.
Reference:
NMP-TR-1 11, On-The-Job Training and Task Performance Evaluation.
START TIME:
PROMPT:
AT this time, GIVE the operator a complete copy of 34SV-E41 -002-2, HPCI Pump Operability.
PROMPT:
AT this time, GIVE the operator Attachment 2 of this JPM (Data has been filled in for this JPM).
PROMPT:
IF the operator addresses the 1ST Book, INFORM the operator that a supervisor has verified the reference data.
1.
The operator evaluates parameters on On Attach. I of 34SV-E41-002-2, and finds Turbine Speed the operator EVALUATES Nr is acceptable.
Turbine Speed Nr data is SATISFACTORY. 3900 rpm (Acceptable Range:
3861 (0.99) to 3939 (1.01) rpm)
( Indicates critical step)
2012-301 ADMIN-4 Page 4 of 12 STEP PERFORMANCE STEP STANDARD I
(COMMENTS) 2.
The operator evaluates parameters on On Attach. 1 of 34SV-E41-002-2, Attachment I and finds Inlet Pressure the operator EVALUATES Inlet (Stopped) (P
- 1) is acceptable.
Pressure (Stopped) (P
- 1) data is SATISFACTORY. 34 psig Acceptable Range: >7 psig.
3.
The operator evaluates parameters on On Attach. I of 34SV-E41-002-2, and finds Inlet Pressure the operator EVALUATES Inlet (Running) (P
- 1) is acceptable.
Pressure (Running) (P
- 1) data is SATISFACTORY. 31 psig Acceptable Range: >7 psig.
- 4 The operator evaluates parameters on At step 7.8.2.1.1 of 34SV-E41-Attachment I and finds Outlet 002-2, the operator Pressure (Running) P0 is NOT EVALUATES Outlet Pressure acceptable.
data IS NOT SATISFACTORY.
1072 psig is not in theAcceptable Range of> 1135 psig.
NOTE: At this time, the operator may elect to inform the Shift Supervisor that Outlet Pressure (Running) P0 is NOT acceptable and HPCI has failed the surveillance. This action IS acceptable.
It IS also acceptable for the operator to complete the review before bringing this to the supervisors attention.
PROMPT:
IF the operator addresses the out of spec. item(s), DIRECT the operator to finish the data package review.
(** Indicates critical step)
2012-301 ADMIN-4 Page 5 of 12 STEP PERFORMANCE STEP STANDARD I
(COMMENTS)
- 5 The operator evaluates parameters on On Attach. 1 of 34SV-E41-002-2, and finds Differential the operator EVALUATES Pressure (2) dPr is NOT acceptable.
Differential Pressure (2) dP data IS NOT SATISFACTORY.
0.88 dPr is not in theAcceptable Range of 0.90 to 1.10 dPr.
NOTE: Ratio Differential Pressure (2) dPr is equal to the Test Value dPr divided by the Reference Value dP
- 1. 1041/1183 = 0.88.
At this time, the operator may elect to inform the Shift Supervisor that Differential Pressure (2) dPr is NOT acceptable and HPCI must be declared inoperable. This action IS acceptable.
It IS also acceptable for the operator to complete the review before bringing this to the supervisors attention.
PROMPT:
IF the operator addresses the out of spec. item(s), DIRECT the operator to finish the data package review.
6.
The operator evaluates parameters on On Attach. I of 34SV-E41-002-2, and finds Flowrate (4) the operator EVALUATES (Q
T) is acceptable.
Flowrate (4) (Qr) data (4250 gpm) is SATISFACTORY.
Acceptable value is 4250 gpm.
- 7 The operator evaluates the stroke time On Attach. I of 34SV-E41-002-2, data for the cooling water valve the operator evaluates the stroke 2P41-F035A.
time data for 2P41-F035A and determines that the valve data is NOT SATISFACTORY.
4.75 seconds has exceeded the Calculated Allowable Time range of 1.5 to 4.5 seconds.
NOTE: At this time, the operator may elect to inform the Shift Supervisor that 2P41-F035A has exceeded the Calculated Allowable Time range of 1.5 to 4.5 seconds and must be immediately retested or declared inoperable.
This action IS acceptable.
It IS also acceptable for the operator to complete the review before bringing this to the supervisors attention.
- Indicates critical step)
2012-301 ADMIN-4 Page 6 of 12 STEP I
PERFORMANCE STEP I
STANDARD I
SAT/UNSAT I
I I
(COMMENTS)
I PROMPT:
IF the operator addresses the out of spec. item(s). DIRECT the operator to finish the data package review.
- 8.
The operator evaluates the stroke time On Attach. 1 of 34SV-E41-002-2, data for the cooling water valve the operator evaluates the stroke 2P41-F035B.
time data for 2P41-F035B and determines that the valve data is NOT SATISFACTORY.
5.2 seconds has exceeded the MAXIMUM Time Limit of 5.0 seconds.
NOTE: At this time, the operator may elect to inform the Shift Supervisor that 2P41-F035B has exceeded the MAXIMUM Time Limit of 5.0 seconds and must be declared inoperable immediately. This action IS acceptable.
It IS also acceptable for the operator to complete the review before bringing this to the supervisors attention.
PROMPT:
WHEN the operator addresses the Out of Spec readings, INFORM the operator to make recommendations based on the findings.
(*
- Indicates critical step)
2012-301 ADMTN-4 Page 7 of 12 STEP PERFORMANCE STEP STANDARD I
(COMMENTS)
The operator determines the The operator determines the procedural requirements.
following procedural requirements:
- HPCI pump is inoperable due to dPr <0.90 per steps 7.8.2.2 & 7.7.3.1
- HPCT pump is inoperable due to Outlet Pressure (Running) P0 <1135 psig per steps 7.8.2.1.1 & 7.7.2.
o 2P41-F035A has exceeded the Calculated Allowable Time (1.5 to 4.5) per step 7.8.4.2 and must be immediately retested OR declared inoperable per step 7.7.7.2.
- 2P41-F035B has exceeded the Maximum Time Limit of 5.0 seconds per step 7.8.4.1 and must be declared inoperable per step 7.7.7.1.
NOTE:
If the operator addresses writing a Condition Report (CR) based on this surveillance, inform the operator that another operator will write the CR.
END TIME:
NOTE:
The terminating cue shall be given to the Operator when:
After JPM step #9 is complete.
With no reasonable progress, the Operator exceeds double the allotted time.
Operator states the task is complete.
TERMINATING CUE:
We will stop here.
EVALUATOR PICK UP the Initiating Cue sheet.
( Indicates critical step)
ATTACHMENT 1
- KEY **
DO NOT give this to applicant SNC PLANT E. I. HATCH
Pg 45 of 66 DOCUMENT TITLE:
I DOCUMENT NUMBER:
Version No:
HPCI PUMP OPERABILITY j
34SV-E41-002-2 30.25 ATTACHMENT 1
Affachment Page TITLE:
HPCI PUMP QUARTERLY 1ST DATA AND ACCEPTANCE CRITERIA 1 of 2 Reference Data Changes:
Is reference data being changed?
(
) Yes (v) No IF YES, list justification for so doing:
(2E41 -Cool)
DATE REF REQD INSTRU MPL REFERENCE ACCEPT.
ALERT RATIO PARAMETER VALUE TEST VALUE ACTION NO.
VALUE RANGE RANGE (3)
TAKEN RANGE (1)
Turbine 0.99 to 2E41-R610 3900 01/18/2010 3900 N/A N/A N/A Speed (Nr) 1.01 RPM Inlet Pressure 2E41-R606 34 01/18/2010 34 7PSIG N/A
<7PSIG N/A Stopped) (P)
Inlet Pressure (Running) 2E41-R606 32 01/18/2010 31 7 PSIG N/A
<7 PSIG N/A (P)
Outlet Pressure 2E41-R601 1215 01/18/2010 1072 N/A N/A N/A N/A (Running)
(P 0)
Differential
<0.90 dPr 0.90 to Pressure (2)
N/A 1183 01/18/2010 1041 N/A or>1.10 1.10 dPr (DPr) dPr Flowrate (4) 2E41-R612 4250 N/A 4250 N/A N/A N/A 1.0 (Qr)
(1)
Pump declared inoperable according to 31G0-INS-001-0.
(2)
Differential pressure must be calculated as: dP Outlet Pressure (pump running)
- Inlet Pressure (Pump running)
(3)
Ratio = Test Value divided by Reference Value (4)
Test value must equal reference value. Ratio for flowrate must equal 1.0.
Page 8 of 12
SNC PLANT E. I. HATCH I
Pg 46 of 66 DOCUMENT TITLE:
DOCUMENT NUMBER:
Version No:
HPCI PUMP OPERABILITY 34SV-E41-002-2 30.25 ATTACHMENT 1
Attachment Page TITLE:
HPCI PUMP QUARTERLY 1ST DATA AND ACCEPTANCE CRITERIA 2 of 2 NOTE*
WHEN calculating OR recording valve stroke times, round off to the nearest tenth second.
COLUMN 2 COLUMN 4 COLUMN 5 COLUMN 3 CALCULATED REFERENCE OPERATING MAXIMUM TIME ALLOWABLE TIME TIME LIMIT TIMED COLUMN 1 TIME (SEC)
BY:
MPL (TYPE)
(SEC)
(SEC)
INIT OPEN CLOSE OPEN CLOSE OPEN CLOSE OPEN CLOSE MIN/MAX MIN/MAX 2P41-F035A 3.0 N/A 1.5 4.5 N/A N/A 4.75 N/A
<5 N/A SMH AOV 2P41-F035B 2.5 N/A 1.25 3.75 N/A N/A 5.2 N/A
<5 N/A SMH AOV IF operating time is less than 1 second, record 1 second as operating time.
VERIFY STROKE TIMES ACCEPTABLE:
DATE:
ATTACHMENT 1
- KEY **
DO NOT give this to applicant Page 9 of 12
ATTACHMENT 2 SNC PLANT E. I. HATCH I
PROVIDE TO APPLICANT Pg 45 of 66 DOCUMENT TITLE:
I DOCUMENT NUMBER:
Version No:
HPCI PUMP OPERABILITY I
34SV-E41-002-2 30.25 ATTACHMENT j_
Attachment Page TITLE:
HPCI PUMP QUARTERLY 1ST DATA AND ACCEPTANCE CRITERIA 1 of 2 Reference Data Changes:
Is reference data being changed?
(
) Yes
( vi) No IF YES, list justification for so doing:
(2E41 -Cool)
DATE REF REQD INSTRU MPL REFERENCE ACCEPT.
ALERT RATIO PARAMETER VALUE TEST VALUE ACTION NO.
VALUE RANGE RANGE (3)
TAKEN RANGE (1)
Turbine 0.99 to 2E41-R610 3900 01/18/2010 3900 N/A N/A N/A Speed (Nr)
1.01 RPM Inlet Pressure 2E41-R606 34 01/18/2010 34 7PSIG N/A
<7PSIG N/A (Stopped) (P)
Inlet Pressure (Running) 2E41-R606 32 01/18/2010 31 7 PSIG N/A
<7 PSIG N/A (Pt)
Outlet Pressure 2E41-R601 1215 01/18/2010 1072 N/A N/A N/A N/A (Running)
(P 0)
Differential
<0.90 dPr 0.90 to Pressure (2)
N/A 1183 01/18/2010 1041 N/A or>1.10 1.10 dPr (DPr) dPr Flowrate (4) 2E41-R612 4250 N/A 4250 N/A N/A N/A 1.0 (Qr)
(1)
Pump declared inoperable according to 3100-INS-O01-0.
(2)
Differential pressure must be calculated as: dP = Outlet Pressure (pump running)
- Inlet Pressure (Pump running)
(3)
Ratio = Test Value divided by Reference Value (4)
Test value must equal reference value. Ratio for flowrate must equal 1.0.
Page 10 of 12
NOTES WHEN calculating Q recording valve stroke times, round off to the nearest tenth second.
COLUMN 1 MPL (TYPE) 2P41-F035A AOV COLUMN 2 REFERENCE TIME (SEC OPEN 3.0 CLOSE N/A COLUMN 3 CALCULATED ALLOWABLE TIME (SEC)
OPEN MIN/MAX 4.5 1.5 CLOSE MIN/MAX N/A N/A COLUMN 4 OPERATING TIME (SEC OPEN 4.75 CLOSE N/A COLUMN 5 MAXIMUM TIME LIMIT (SEC OPEN
<5 CLOSE N/A TIMED BY:
INIT SMH j[ operating time is less than 1 second, record 1 second as operating time.
VERIFY STROKE TIMES ACCEPTABLE:
DATE:
SNC PLANT E. I. HALcI-U ATTACHMENT 2 PROVIDE TO APPLICANT DOCUMENT TITLE:
DOCUMENT NUMBER:
Version No:
HPCI PUMP OPERABILITY 34SV-E41-002-2 30.25 ATTACHMENT 1
Attachment Page TITLE:
HPCI PUMP QUARTERLY 1ST DATA AND ACCEPTANCE CRITERIA 2 of 2 PQ 46 of 66 2P41 -F035B 2.5 N/A 1.25 3.75 N/A N/A 5.2 N/A
<5 N/A SMH AOV Page 11 of 12
UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:
1.
Unit 2 is at 100% power.
2.
An In-Service Test (1ST) has just been completed for the HPCI pump JAW 34SV-E41-002-2, HPCI Pump Operability.
INITIATING CUES:
Review Attachment I of 34SV-E41 -002-2, HPCI Pump Operability.
Complete any calculations required by the surveillance data sheets.
Inform the Shift Supervisor of your results and any recommendations or procedural requirements based on the results.
Page 12 of 12
DRAFT Southern Nuclear E. I, Hatch Nuclear Plant Operations Training JPM Admin 5 ALL SOUTHERN COMPANY TITLE RADIATION EXPOSURE CALCULATION AND REQUIRED AUTHORIZATION AUTHOR MEDIA NUMBER TIME Anthony Ball 2012-301 ADMIN-5 15 Minutes RECOMMENDED BY APPROVED BY DATE
SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH Page 1 of I FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code:
OPERATIONS TRAINING Media Number: 2012-301 ADMIN-5 Rev. No.
Date 1
Reason for Revision Authors Supvs I
Initials Initials 01 Revision for HLT7 NRC Exam. After NRC Exam, ARB Media Number will be changed to LRJP-10020-01.
2012-301 ADMIN-5 Page 1 of 5 UNIT 1
(
)
UNIT 2 (X)
TASK TITLE:
Radiation Exposure Calculation and Required Authorization.
JPM NUMBER:
2012-301 ADMIN-5 TASK STANDARD:
The task shall be complete when it has been determined the job cannot be performed without exceeding annual administrative radiation exposure limits, and determining the level of approval to exceed the annual administrative radiation exposure limit.
TASK NUMBER:
N/A OBJECTIVE NUMBER:
LT30008.01 K/A CATALOG NUMBER: Generic 2.3.4 K/A CATALOG JTA IMPORTANCE RATING:
RO 3.2 SRO 3.7 OPERATOR APPLICABILITY:
Nuclear Plant Operator (NPO) / Senior Reactor Operator (SRO)
GENERAL
REFERENCES:
Unit 2 6OACHPX-001-0 (current version)
REQUIRED MATERIALS:
Unit 2 6OAC-HPX-001-0 (current version)
APPROXIMATE COMPLETION TIME:
15 Minutes SIMULATOR SETUP:
N/A
EVALUATOR COPY UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:
1.
You are a radiation worker at Hatch and have been assigned to perform a job in the Unit 2 Clean Up Phase Separator (CUPS) room.
2.
Gamma radiation is the only type of radiation of concern for this particular job (no airborne, Beta or Alpha).
3.
Your job inside the CUPS room, will take 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
4.
Your total exposure (TEDE) for the year so far has been confirmed to be 1400 mrem.
5.
One of the radiation fields you will work in for 20 minutes is 4500 mremlhour (Gamma radiation).
6.
The other radiation field that you will work in for 40 minutes is 1200 mremlhour (Gamma radiation).
7.
The dose in the travel path to the CUPS room is 1800 mremlhr.
8.
Travel time through the 1800 mrem/hr field to the CUPS area is 6 minutes EACH WAY.
INITIATING CUES:
Calculate the Total exposure you will receive for the job.
Determine if any Administrative Radiation Exposure Limits will be exceeded.
Considering your current exposure (1400 mrem) and that which will be received from this job, determine who must authorize the exposure, if anyone, lAW 6OAC-HPX-001-0.
2012-301 ADMIN-5 Page 3 of 5 STEP I
SAT/UNSAT I
PERFORMANCE STEP STANDARD (COMMENTS)
IF THEN U
Human performance tools, safety, PPE met (1), AND U
For initial trg all steps completed correctly OR PASS U
For continuing trg, critical steps (if used) completed correctly U
Mark the JPM as a FAIL FAIL IU Above standards not met (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have liffle or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.
Reference:
NMP-TR-1 11, On-The-Job Training and Task Performance Evaluation.
START TIME:_______
NOTE: If the applicant addresses 8.1.2.1 which states: Prior to an individuals first work assignment in which the individual is likely to receive in excess of 2% of the limits in 8.1.1, the individual MUST submit a signed statement indicating the amount of occupational radiation exposure received during the current calendar year from sources of radiation possessed by other licensees. INFORM the applicant that this form has been signed.
- 1.
The applicant calculates exposure in (4,500 mremlhr) X 20 mm
=
the 4,500 mremlhour field.
60 mm 1500 mrem.
The applicant calculates exposure in the 1200 mrem/hour field.
For INITIAL Operator Programs:
For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.
- 2 (1200 mremlhr) X 40 mm 60 mm 800 mrem
- 3 The applicant calculates the dose (1800 mremlhr) X 6 mm x 2 trips received from travel time.
60 mm
= 360 mrem.
2012-301 ADMIN-5 Page 4 of 5 STEP I
I SAT/UNSAT I
PERFORMANCE STEP STANDARD (COMMENTS) 1
- 4 The applicant calculates total exposure:
1400 1500 800 360 4060 mrem Total
- 5 The applicant determines that the The Hatch Administrative limits Hatch Annual Administrative are 2,000 and 4000 mremlyear.
Radiation Exposure limit will be (6OAC-HPX-001-0 step 8.2.1) exceeded while performing the work.
NOTE: The applicant may address being on the Margin List when within 400 mrem of the administrative exposure limit. It is not necessary for the applicant to discuss the requirements of the margin list for this JPM.
PROMPT:
IF the applicant addresses the margin list, STATE that the Health Physics department is taking appropriate actions for Margin List requirements based on expected exposures for this job.
- 6.
The applicant determines the With available exposure authorization requirements to exceed confirmed, authorization must be the Annual Administrative limits, written approvals from an HP Supervisor and from the Plant Manager. (Step 8.2.2)
NOTE:
The terminating cue shall be given to the Operator when:
After JPM step #6 is complete.
With no reasonable progress, the Operator exceeds double the allotted time.
Operator states the task is complete.
TERMINATING CUE:
We will stop here.
END TIME:_______
EVALUATOR PICK UP the Initiating Cue sheet.
Page 5 of 5 UNIT 2 READ TO THE APPLICANT INITIAL CONDITIONS:
1.
You are a radiation worker at Hatch and have been assigned to perform a job in the Unit 2 Clean Up Phase Separator (CUPS) room.
2.
Gamma radiation is the only type of radiation of concern for this particular job (no airborne, beta or alpha).
3.
Your job inside the CUPS room, will take 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
4.
Your total exposure (TEDE) for the year so far has been confirmed to be 1400 mrem.
5.
One of the radiation fields you will work in for 20 minutes is 4500 mremlhour (gamma radiation).
6.
The other radiation field that you will work in for 40 minutes is 1200 mremlhour (gamma radiation).
7.
The dose in the travel path to the CUPS room is 1800 mremlhr.
8.
Travel time through the 1800 mremlhr field to the CUPS area is 6 minutes each way.
INITIATING CUES:
Calculate the total exposure you will receive for the job.
Determine if any administrative radiation exposure limits will be exceeded.
Considering your current exposure (1400 mrem) and that which will be received from this job, determine who must authorize the exposure, if anyone, JAW 6OAC-HPX-001-0.
DRAFT Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Admin 6 SRO ONLY SOUTHERN COMPANY TITLE EMERGENCY CLASSIFICATION AND NOTIFICATION (NEW EALS)
AUTHOR MEDIA NUMBER TIME CRITICAL Anthony Ball 2012-301 ADMIN-6 15.0/15.0 Minutes RECOMMENDED BY APPROVED BY DATE N/R
SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH Page 1 of 1 FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code:
OPERATIONS TRAINING Media Number: 2012-301 ADMIN-6 01 Rev. No. J Date J
Reason for Revision Authors Supvs i.
i Initials Initials 00 04/30/07 Initial development CME RAB 1 1/04/10 Added Task and HU Pass/Fail criteria. Updated EU CME Southern_Company_logo.
02 01/12/11 Updated references to NMP-EP-1 10 and MCK DNM NMP-EP-1 11 03 General revision for use on NRC Exam 2012-301.
ARB After NRC Exam, Media Number will be changed to LR-JP-2506 1-03.
2012-301 ADMIN-6 Page 1 of 7 UNIT 1 (X)
UNIT 2 (X)
TASK TITLE:
Emergency Classification and Notification (NEW EALS)
JPM NUMBER:
2012-301 ADMIN-6 TASK STANDARD:
The task shall be completed when the event has been classified per NMP-EP-1 10, the ENN form NMP-EP-1 11 Figure 1 has been completed, and offsite notifications have been directed.
TASK NUMBER:
200.052 OBJECTIVE NUMBER:
200.052.A PLANT HATCH JTA IMPORTANCE RATING:
RO 4.67 SRO 4.04 K/A CATALOG NUMBER: Generic 2.4.4 1 K/A CATALOG JTA IMPORTANCE RATING:
RO 2.9 SRO 4.6 OPERATOR APPLICABILITY:
Senior Reactor Operator (SRO)
- GENERAL
REFERENCES:
Unit 1 & 2 NMP-EP-1 10 (current version)
NMP-EP-1 1 1 (current version)
F REQUIRED MATERIALS:
Unit 1 & 2 NMP-EP-1 10 (current version)
NMP-EP-111 FIGURE 1 (current version)
APPROXIMATE COMPLETION TIME:
15.0/15.0 Minutes SIMULATOR SETUP:
N/A
EVALUATOR COPY UNIT1&2 READ TO THE OPERATOR INITIAL CONDITIONS:
1.
Unit 2 is in a LOSP due to a failure of the 2D and 2C SUTs.
2.
The Reactor scrammed and All rods fully inserted on the scram signal.
3.
For the last 15 minutes, Only Emergency Diesel 2A has been running and is supplying power to 2E 4160 VAC bus.
4.
Emergency Diesel Generators lB and 2C start attempts have not been successful.
5.
All other Unit 2 parameters are normal.
6.
The following Unit 1 conditions exists:
100% power All parameters normal INITIATING CUES:
Determine the emergency classification that should be declared.
Complete the ENN form NMP-EP-1 11 Figure 1 for offsite notifications.
Direct the operator to make the proper offsite notifications.
Current time is:
2012-301 ADMIN-6 Page 3 of 7 STEP I
I PERFORMANCE STEP STANDARD (COMMENTS) 1 I
SAT/UNSAT IF THEN U
Human performance tools, safety, PPE met (1), AND U
For initial trg all steps completed correctly OR PASS U
For continuing trg, critical steps (if used) completed correctly U
Mark the JPM as a FAIL FAIL U
Above standards not met (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.
Reference:
NMP-TR-1 11, On-The-Job Training and Task Performance Evaluation.
NOTE: For the completion of this JPM, there is TWO SEPARATE CLOCKS.
The CLASSIFICATION must be made within 15 minutes of the initial prompt.
When the classification is made, a second clock starts. The ENN form and direction to make the NOTIFICATIONS MUST BE COMPLETED WITH 15 MINUTES of that clock start.
1st START TIME:_______
1.
Operator identifies the procedure Operator has identified the correct needed to perform the task, procedure as NMP-EP-1 10.
- 2.
Operator classified event per Operator has CLASSIFIED the NMP-EP-1 10.
event as an ALERT EMERGENCY.
NOTE: The expected classification is an ALERT based on IC# SA5, Single power source to the ESF busses and an additional failure will result in a station blackout. If follow-up questioning reveals that a classification was declared and based on another IC #, the classification should be evaluated for validity.
1st END TIME:________
( Indicates critical step)
For INITIAL Operator Programs:
For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.
STEP NOTE: To successfully complete the ENN form, ALL STEPS HIGHLIGHTED IN YELLOW must be properly completed.
201 2-301 ADMIN-6 Page 4 of 7 SAT/UNSAT (COMMENTS)
To be properly completed, the ENN form must have all the required steps completed with correct information. APPLICABLE HIGHLIGHTED steps must contain sufficient information to describe the event.
NOTE:
The terminating cue shall be given to the Operator when:
After 3PM step #4 is complete.
With no reasonable progress, the Operator exceeds double the allotted time.
Operator states the task is complete.
TERMINATING CUE: We will stop here.
EVALUATOR PICK UP the Initiating Cue sheet.
2 END TIME:_______
PERFORMANCE STEP STANDARD NOTE: The classification IS MADE when the operator STATES OR WRITES the classification. This starts the second clock.
PROMPT:
WHEN the operator enquires about meteorological conditions, GIVE the operator the MIDAS Information Sheet.
2° START TIME:________
- 3 Operator properly completes the ENN Operator has properly form per NMP-EP-l 11.
COMPLETED NMP-EP-1 11 FIGURE 1, Southern Nuclear Emergency Notification form.
(** Indicates critical step)
ATTACHMENT 1 ** KEY ** DO NOT GIVE TO APPLICANT
(*Ma not be available for Initial Precipitation i;1 DECLARATION
- 11. A?FECTED UNIT(S):
- 12. UNIT STATUS:
(Unaffected Unit(s) Status Not Required for Initial Notifications)
- 13. REMARKS:_________________
Above normal operating limits Degrading Wind Speed mph*
FOLLOW-UP INFORMATION (Lines 14 through 16 Not Required for Initial Notifications)
EMERGENCY RELEASE DATA NOT REQUIRED IF LINE 6 A IS SELECTED.
- 14. RELEASE CHARACTERIZATION:
TYPE:
Elevated Mixed Ground UNITS:
Ci Ci/sec
.tCi/sec MAGNITUDE:
Noble Gases:__________ lodines:___________ Particulates:__________ Other:
FORM: [ Airborne Start Time Date _/_
/._Stop Time Date J_L_
fLiquid Start Time Date.._/_ _j_.Stop Time Date J_J_.
- 15. PROJECTION PARAMETERS:
Projection performed:
16.
PROJECTED DOSE:
- 17. APPROVED BY:
NOTIFIED BY:
Projection period:
Time Date DISTANCE Site boundary 2 Miles 5 Miles 10 Miles RECEIVED BY:
Time (To be completed by receiving organization)
Southern Nuclear Operating Company Emergency I
NMP-EP-1 11 JTHERNjZS.
Implementing I
Emergency Notifications Version 6.0 COMPANY Procedure Page 36 of 48 Figure 1 Emergency Notification Form (page 1 of 2) 1.NDRILL I1ACTUALEVENT MESSAGE#____
- 2. INITIAL FOLLOW-UP NOTIFICATION: TIME DATE
_L__I_ AUTHENTICATION #_____
- 3. SITE:
Confirmation Phone 4/
- 4. EMERGENCY CLASSIFICATION:
( UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY EASED ONBAL#________
EAL DESCRIPTION:______________________________________
5, PROTECTIVE ACTION RECOMMENDATIONS:
j NONE I EVACUATE Advise Remainder ofEPZ to Monitor Local Radio/TV Stations/Tone Alert Radios for Additional Information and Consider the use ofEl (potassiumiodide) in accordance with State plans and policy.
OTHER
- 6. EMERGENCYRELEASE:
None Is Occurring Has Occurred
- 7. RELEASE SIGNIFICANCE:
- 8. EVENT PROGNOSIS:
- 9. METEOROLOGICAL DATA:
j Not applicable Within normal operating limits j Improving
[} Stable Wind Direction from g
] TERMINATION IJ1I Under evaluation Stability Class*
Time Date _.__/
/
UI.._% Power U2 __% Power Shutdown at Time Date
/
I Shutdown at Time Date._J.j___
Hours Estimated Release Duration
_________Hours Accident Type:
TEDE (rnrem)
Adult Thyroid CDE (mrem)
Time______
Title Page 5 of 7
MIDAS iNFORMATION METEOROLOGICAL 1 OM WIND SPD 1 OOM WIND SPD 1 OM WIND DIR 1 OOM WIND DIR 1Y33-R601 1Y33-R603 1Y33-R601 1Y33-R603 5.0 5.0 130 I30 AMBIENT TEMP DELTA T DELTA T RAINFALL (F) 1 OM 60-10 100-10 15 MIN. AVG 54
-1.6
-2.9
.000 RADIOLOGICAL MAIN STACK U 1 RX. BLDG. VENT U2 RX. BLDG. VENT NORMAL RANGE KAMAN NORMAL RANGE KAMAN NORMAL RANGE KAMAN 1D1J-K600A 1D11-R631 1D11-K619A 1D11-R631 2D11-K636A 2D11-R631 2.OOEO1 5,04E01 4.OOEO1 1D11-K600B 1D11-K619B 2D11-K636B 2.OOEO1 4.OOEO1 STABILITY CLASS D
UNIT1&2 READ TO THE OPERATOR INITIAL CONDITIONS:
1.
Unit 2 is in a LOSP due to a failure of the 2D and 2C SUTs.
2.
The Reactor scrammed and All rods fully inserted on the scram signal.
3.
For the last 15 minutes, Only Emergency Diesel 2A has been running and is supplying power to 2E 4160 VAC bus.
4.
Emergency Diesel Generators lB and 2C start attempts have not been successful.
5.
All other Unit 2 parameters are normal.
6.
The following Unit 1 conditions exists:
100% power All parameters normal INITIATING CUES:
Determine the emergency classification that should be declared.
Complete the ENN form NMP-EP-1 11 Figure 1 for offsite notifications.
Direct the operator to make the proper offsite notifications.
Current time is:
Page 7 of 7